ML081090248
| ML081090248 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, 07200061  |
| Issue date: | 04/16/2008 |
| From: | Vias S Division Reactor Projects II |
| To: | Stall J Florida Power & Light Co |
| Shared Package | |
| ML081090236 | List: |
| References | |
| IR-08-001, IR-08-007 | |
| Download: ML081090248 (13) | |
See also: IR 05000335/2008007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER
61 FORSYTH STREET, SW, SUITE 23T85
ATLANTA, GEORGIA 30303-8931
April 16, 2008
Florida Power and Light Company
ATTN: Mr. J. A. Stall, Senior Vice President
Nuclear and Chief Nuclear Officer
P. O. Box 14000
Juno Beach, FL 33408-0420
SUBJECT:
ST. LUCIE NUCLEAR PLANT - NRC ISFSI INSPECTION REPORT
05000335/2008007, 05000389/2008007, and 07200061/2008001
Dear Mr. Stall:
This inspection report covers two visits made by the United States Nuclear Regulatory
Commission (NRC) to your Saint Lucie Units 1 and 2 Nuclear Plant Independent Spent Fuel
Storage Installation (ISFSI) between February 25 and March 14, 2008. The purpose of the site
visits was to inspect your spent fuel storage pre-operational (dry run) testing activities and to
observe your first loading of the NUHOMS-HD storage system. The first NUHOMS-HD canister
was loaded and placed in storage at the ISFSI on March 15, 2008. The enclosed inspection
report documents the results of the inspection, which were discussed on February 29, 2008,
with Mr. Gordon Johnston and other members of your staff. The inspection covered all aspects
associated with the preparation, movement, and placement of spent fuel into the ISFSI facility
and consisted of field observations, extensive examination of procedures and documents, and
interviews with personnel. Dry run preparations were thorough and individuals appropriately
trained and qualified in the performance of tasks. Sound, conservative decision-making was
noted throughout the performance of the dry run and the initial loading of spent fuel into the
ISFSI facility. Activities were implemented in a safe manner. The enclosed report presents the
results of that inspection. Based on results of this inspection, no violations or findings of
significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
2
Room or from the Publicly Available Records (PARS) component of NRCs document system
(ADAMS). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/readingrm/adams.html. (The Public Electronic Reading Room).
Sincerely,
/RA/
Steven J. Vias, Chief
Technical Support Branch
Division of Reactor Projects
Docket Nos.: 50-335, 50-389, and 72-061
Enclosure: Saint Lucie Nuclear Plant - Independent Spent Fuel Storage Installation (ISFSI) Dry
Run and Initial Loading Inspection Report
Attachments: 1. Supplemental Information
2. Inspector Notes
_________________________
OFFICE
RII:DRS
RIV:DNMS
HQ:
RIV:
HQ
HQ:NSIR
HQ
RII:DRP
IGNATURE
RPC
Telecom
SJV
AME
RCarrion
VEverett
FJacobs
JParrott
RTemps
RBerry
NSantos
SVias
DATE
04/10/2008
04/09/2008
04/09/2008
04/09/2008
04/10/2008
04/09/2008
04/09/2008
04/16/2008
-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES NO
3
cc w/encl:
Gordon L. Johnston
Site Vice President
St. Lucie Nuclear Plant
Electronic Mail Distribution
Christopher R. Costanzo
Plant General Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
Bill Parks
Operations Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
Terry L. Patterson
Licensing Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
Rajiv S. Kundalkar
Vice President
Nuclear Technical Services
Florida Power & Light Company
Electronic Mail Distribution
Don E. Grissette
Vice President
Nuclear Training and Performance
Improvement
Florida Power & Light Company
Electronic Mail Distribution
Seth B. Dunston
Training Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
M. S. Ross
Managing Attorney
Florida Power & Light Company
Electronic Mail Distribution
Marjan Mashhadi
Senior Attorney
Florida Power & Light Company
Electronic Mail Distribution
William A. Passetti
Bureau of Radiation Control
Department of Health
Electronic Mail Distribution
Craig Fugate
Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
J. Kammel
Radiological Emergency Planning
Administrator
Department of Public Safety
Electronic Mail Distribution
Douglas Anderson
County Administrator
St. Lucie County
2300 Virginia Avenue
Ft. Pierce, FL 34982
Mano Nazar
Senior Vice President
and Nuclear Chief Operating Officer
Florida Power & Light Company
Electronic Mail Distribution
4
Letter to J. Art Stall from Steven J. Vias dated April 16, 2008
SUBJECT:
ST. LUCIE NUCLEAR PLANT - NRC ISFSI INSPECTION REPORT
05000335/2008007, 05000389/2008007, and 07200061/2008001
Distribution w/encl:
C. Evans, RII
L. Slack, RII
OE Mail (email address if applicable)
RIDSNRRDIRS
PUBLIC
B. Mozafari, NRR (PM: STL, TP)
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket Nos.:
50-335, 50-389,72-061
License:
Report No:
05000335/2008007; 05000389/2008007; and 07200061/2008001
Licensee:
Florida Power and Light Company (FPL)
Facility:
Saint Lucie Units 1 & 2
Location:
6351 South Ocean Drive
Jensen Beach, FL 34957
Dates:
February 25 through March 14, 2008
Inspectors:
Region II DRS Inspector - Team Leader
Vincent Everett
Senior Health Physics Inspector
Frank Jacobs
HLWRS Senior Project Manager
HLWRS Senior On-Site Licensing
Representative - Yucca Mountain
Robert Temps
SFST Senior Safety Inspector
Accompanying
Rollie Berry
SFST Structural Engineer
Personnel:
Norma Garcia-Santos
SFST Project Manager
Approved By:
Steven J. Vias, Chief
Technical Support Branch
Division of Reactor Projects
Attachments:
Supplemental Information
Inspector Notes
Enclosure
EXECUTIVE SUMMARY
Saint Lucie Nuclear Plant
NRC Inspection Report 05000335/2008007; 05000389/2008007; and 07200061/2008001
Florida Power and Light (FPL) had selected the NUHOMS-HD Horizontal Modular Storage
System for dry storage of spent nuclear fuel at the Saint Lucie Nuclear Plant. The Nuclear
Regulatory Commission (NRC) had certified the NUHOMS-HD cask system for storage of
irradiated fuel under Certificate of Compliance No. 72-1030 on January 10, 2007.
From February 25-29, 2008, a team of five inspectors performed two evaluations. The first
evaluation was to determine if the ISFSI personnel had been trained, the equipment had been
tested, and the procedures had been developed to the extent necessary to safely load spent
fuel into dry storage at the ISFSI. The second evaluation was to determine if the Saint Lucie
station programs were adequate for continued maintenance and operation of the ISFSI once it
was loaded. The results of these two evaluations were discussed during a debriefing on
February 29, 2008, with Mr. Gordon Johnston and other members of the staff.
From March 9-14, 2008, NRC inspectors observed the first loading of spent fuel into dry storage
using the NUHOMS Storage System. The purpose was to verify that the first loading was
performed safely, in accordance with approved procedures, and within the Technical
Specification limits.
The following provides a summary of the results of the inspection. Details are provided in the
Inspector Notes contained in Attachment 2 to this report.
Spent Fuel Cask Crane
The licensee certified its Unit 1 and Unit 2 spent fuel cask cranes as single-failure
proof in accordance with NUREG-0612 and NUREG-0554 in a letter to the NRC
dated December 11, 2003. An extensive review was performed and documented
by the crane manufacturer to verify compliance with the NUREG requirements.
A review of the crane design features by the NRC inspectors against selected
NUREG requirements found that for those features reviewed, the crane met the
single-failure proof criteria established by the NRC. (Attachment 2, Crane
Design, pages 1-10 and Heavy Loads, pages 31-32)
The crane, hooks, and wire rope were inspected, tested, and maintained in
accordance with the ASME Code, NUREG-0554, NUREG-0612, and the crane
manufacturers instructions. (Attachment 2, Crane Inspection/Maintenance,
Pages 10-15)
The crane and hook had been load tested and operated in accordance with the
ASME Code, NUREG-0554, and NUREG-0612. (Attachment 2, Crane Load
Testing and Crane Operation, Pages 15-20)
3
Enclosure
Canister Drying and Helium Backfill Operations
The canister was vacuum dried and backfilled with helium to the pressures
specified by Technical Specifications. The drying and backfilling operations were
completed within the time limits specified. (Attachment 2, Drying/Helium Backfill,
Pages 20-22)
Emergency Planning
The Emergency Plan had been expanded to include the ISFSI. An Emergency
Action Level (EAL) had been developed for accidents involving the ISFSI.
(Attachment 2, Emergency Planning, Page 22)
Fire Protection
The Fire Protection Plan had been expanded to include the ISFSI. Emergency
response training had been provided for off-site responders. (Attachment 2, Fire
Protection, Pages 22-23)
Fuel Selection and Verification
The spent fuel assemblies selected for loading into the first NUHOMS-HD
canister met the Technical Specification requirements for assembly type,
cladding integrity, decay heat load, and physical design characteristics.
(Attachment 2, Fuel Selection/Verification, Pages 23-25)
A canister loading plan had been developed based on the combination of spent
fuel assembly enrichment, burnup, cooling time, and decay heat. (Attachment 2,
Fuel Selection/Verification, Pages 25-26)
The Technical Specification actions required for spent fuel mis-loading had been
incorporated into the loading procedure. (Attachment 2, Fuel
Selection/Verification, Page 27)
General License Conditions
The NUHOMS-HD cask design was compatible with the Saint Lucie
10 CFR Part 50 requirements. There were no items identified that required NRC
review or approval prior to use of the NUHOMS-HD system. (Attachment 2,
General License, Page 27)
The licensee had calculated the dose to the public at the site boundary from
normal ISFSI operations. The dose was within the limits allowed by
10 CFR 72.104. (Attachment 2, General License, Pages 27-28)
The soil structure under the ISFSI pad was determined not to be subject to
liquefaction during a Safe Shutdown Earthquake. (Attachment 2, General
License, Page 28)
4
Enclosure
The Horizontal Storage Modules (HSMs) were placed on the ISFSI pad in an
array that was consistent with the Technical Specifications. (Attachment 2,
General License, Page 28-29)
The NUHOMS-HD cask system design parameters were bounded by the Saint
Lucie Power Station reactor site parameters. (Attachment 2, General License,
Pages 29-31)
Heavy Loads
All lifts of the transfer cask and canister were made under the Saint Lucie Power
Station heavy loads requirements and procedures, as documented through a
10 CFR 50.59 evaluation. (Attachment 2, Heavy Loads, Pages 31-32)
A safe load path had been established for transfer cask movements, meeting the
requirements of NUREG-0612. (Attachment 2, Heavy Loads, Page 32)
Procedures and Technical Specifications
Procedures were established to ensure that the NUHOMS-HD cask storage
system technical specification requirements for inspection, maintenance,
operation, and surveillance were implemented. These procedures were
implemented during the first NUHOMS cask system loading. (Attachment 2,
Procedures and Technical Specifications, Pages 32-35)
Quality Assurance
The licensees 10 CFR Part 50 Quality Assurance Program had been expanded
to include the ISFSI. The licensee had established measures for ensuring that:
instruments used to verify compliance with the Technical Specifications were
calibrated; conditions adverse to quality were promptly identified and corrected;
dry fuel storage components were properly stored to prevent degradation; and
purchased material, equipment, and services conformed to procurement
documents. (Attachment 2, Quality Assurance, Pages 35-38)
Radiation Protection
Measures were established to limit personnel exposures to as low as reasonably
achievable (ALARA). Considerations for exposure and contamination control
had been incorporated into the procedures for canister gas sampling and re-
flooding during unloading. The transfer cask annulus seal survey was
accomplished in the proper sequence to ensure the canister did not exit the
building with contamination above the limits. The total exposure estimated for
the first canister was 0.128 person-rem but could be revised once the TLDs are
processed and the results received. This value was low compared to other
reactor sites which have loaded canisters. A range of 0.300 to 0.700 person-rem
has typically been reported by the industry for first loadings. (Attachment 2,
Radiation Protection, Pages 38-39)
Criticality prevention and monitoring during cask loading was implemented. The
minimum spent fuel pool boron concentration required by Technical
5
Enclosure
Specifications was established. Criticality monitoring and alarm systems were
installed in all areas where spent fuel was handled. (Attachment 2, Radiation
Protection, Page 39)
The licensee had performed an analysis to confirm that the limits of
10 CFR 72.104 would not be exceeded during normal operation of the ISFSI
when fully loaded. The Horizontal Storage Module (HSM) dose rates had been
established based on the analysis. (Attachment 2, Radiation Protection, Pages
39-40)
The licensee had established a special program to assess the neutron dose to
workers when the water was removed from the canister and a higher energy
spectrum would result in the areas near the cask. (Attachment 2, Radiation
Protection, Page 40)
Training
The training and certification of personnel for ISFSI activities was conducted
under the licensees 10 CFR Part 50 Training Program. Only those personnel
who had completed all phases of the training were certified to operate the ISFSI
equipment and systems. (Attachment 2, Training, Pages 40-41)
The training had been conducted in the classroom and in the field. The
classroom training used the training modules that were developed in
conformance with the NUHOMS FSAR requirements. The field training had been
conducted during the dry run training exercise (pre-operational testing). The
tasks that were taught during the dry run were consistent with the conditions of
the Certificate of Compliance. All ISFSI personnel had completed the training.
(Attachment 2, Training, Pages 41-43)
Page 1of 3
Attachment 1
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel
G. Adams, ISFSI Licensing
R. Bashwiner, Operations - Senior Reactor Operator
E. Belizar, Manager of Projects
M. Bladek, Operations
D. Ceechett, Work Control
L. Church, ISFSI Project Manager of Operations
T. Cosgrove, Engineering
C. Costanzo, Plant General Manager
J. DiVentura, Projects
A. Fata, Director of Projects
K. Frehafer, Licensing
C. Gears, Projects
J. Harmon, RE
J. Heinold, Chemistry
G. Hollinger, Projects
R. Hriber, Maintenance
W. Jenkins, ISFSI Project
R. Lay, Maintenance Training
G. Johnston, Site Vice President
A. Keary, Work Control
M. Koch, Radiation Protection Supervisor
T. Lehmann, Nuclear Projects
C. Lloyd, Nuclear Assurance
R. Margolis, RE
C. Martin, Radiation Protection
W. Mead, RE
M. Moore, Radiation Protection Manager
M. Moran, Engineering
B. Mouring, Radiation Protection
E. Mullins, Mechanical Maintenance Supervisor
L. Neely, Work Control Manager
M. Page, Operations
T. Patterson, Licensing Manager
J. Porter, Engineering
G. Pustover, Quality Assurance
D. Rey, Maintenance Manager
L. Ruff, Projects
R. Russo, ISFSI Civil Engineer
M. Seidler, Security
P. Sharp, Nuclear Fuels Engineer
D. Taylor, Health Physics Supervisor
R. Vandevender, Contractor
R. Young, Systems Engineer
A. Zielonka, Project Engineering Manager
Page 2 of 3
Attachment 1
Transnuclear/TriVis Personnel
J. Chapman
J. Kelly
American Crane & Equipment Corporation
M. Fitzgerald, Project Manager
INSPECTION PROCEDURES USED
60854.1
Pre-operational Testing of Independent Spent Fuel Storage Installations at
Operating Plants
60855.1
Operation of an Independent Spent Fuel Storage Installation at Operating Plants
60856.1
Review of 10 CFR 72.212(b) Evaluations at Operating Plants
60857
Review of 10 CFR 72.48 Evaluations
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed
None
Discussed
None
LIST OF ACRONYMS USED
ACECO
American Crane and Equipment Corporation
As Low As Reasonably Achievable
Area Radiation Monitor
American Society of Mechanical Engineers
AWS
American Welding Society
BPRA
Burnable Poison Rod Assembly
cm
centimeter
Certificate of Compliance
CR
Condition Report
dpm
disintegrations per minute
Emergency Action Level
Emergency Plan Implementing Procedure
F
Fahrenheit
FHB
Fuel Handling Building
Florida Power and Light
High Efficiency Particulate Air
HSM
Horizontal Storage Module
Page 3 of 3
Attachment 1
Independent Spent Fuel Storage Installation
keV
kiloelectron Volt
kW
kilowatt
lb
pound
LCO
Limiting Condition for Operation
MeV
Megaelectron Volt
MMP
Mechanical Maintenance Procedure
mph
miles per hour
mrem
milli-rem
Magnetic Particle
NFAH
Non-Fuel Assembly Hardware
NRC
Nuclear Regulatory Commission
On-Job Training
PMB
Preventive Maintenance Bases
ppm
parts per million
psig
pounds per square inch gage
Quality Assurance
ref-cc/sec
reference cubic centimeters per second
Systematic Approach to Training
Significant Conditions Adverse to Quality
Safety Evaluation Report
Structures, Systems, and Components
Soil Structure Interaction
Thermoluminescent Dosimetry
TPA
Thimble Plug Assembly
Updated Final Safety Analysis Report
VPI
Vibration Suppression Insert